Woodhead Publishing Series in Energy

Foreword

Preface

Chapter 1: Overview of ageing and degradation issues in light water reactors (LWRs)

1.1 Introduction

1.2 Degradation mechanisms and materials ageing issues in nuclear steam supply systems (NSSS)

1.3 Radiation effects

1.4 Degradation mechanisms of specific nuclear reactor structures

1.5 Conclusions

Chapter 2: Corrosion in pressurized water reactors (PWRs)

Abstract:

2.1 Introduction

2.2 Pressurized water reactors and the main types of corrosion

2.3 Major components experiencing corrosion

2.4 Conclusion

Chapter 3: Creep deformation of materials in light water reactors (LWRs)

Abstract:

3.1 Introduction

3.2 Standard creep equations

3.3 Identifying the mechanisms of creep

3.4 Rate controlling mechanisms and activation energy

3.5 Transitions in creep mechanisms

3.6 Modeling creep life: extrapolation of strain and rupture data

3.7 Case studies illustrating the role of other factors

3.8 Creep of zirconium alloys used for LWR cladding

Chapter 4: Properties of zirconium alloys and their applications in light water reactors (LWRs)

Abstract:

4.1 Introduction

4.2 Fuel assembly designs

4.3 Effects of irradiation on zirconium alloys

4.4 Mechanical properties of zirconium alloys

4.5 Corrosion of zirconium alloys

4.6 Dimensional stability of zirconium alloys

4.7 Future trends and research needs

4.8 Sources of further information

4.9 Acknowledgements

Chapter 5: Performance and inspection of zirconium alloy fuel bundle components in light water reactors (LWRs)

Abstract:

5.1 Introduction

5.2 Materials performance during normal operational conditions

5.3 Materials performance during accidents

5.4 Materials performance during interim dry storage

5.5 Inspection methods

5.6 Future trends and research needs

5.7 Sources of further information and advice

5.8 Acknowledgements

Chapter 6: Ageing of electric cables in light water reactors (LWRs)

6.1 Introduction

6.2 Cable degradation issues

6.3 Analysis and assessment methods

6.4 Residual life modeling

6.5 Development and application of cable ageing mitigation routes

Chapter 7: Materials management strategies for pressurized water reactors (PWRs)

Abstract:

7.1 Introduction

7.2 Materials management strategies

7.3 Management techniques: development and application

7.4 Case studies of management strategies

Chapter 8: Materials management strategies for VVER reactors

Abstract:

8.1 Introduction

8.2 Description of operating VVER reactors

8.3 Ageing of the VVERs – plant operational experience

8.4 Ensuring safety for a long-term operation

8.5 Plant programmes credited for long-term operation

8.6 Conclusion

Chapter 9: Materials-related problems faced by light water reactor (LWR) operators and corresponding research needs

Abstract:

9.1 Introduction

9.2 Fuel and cladding materials – the first fission barrier

9.3 The primary system – the second fission barrier

9.4 The containment structure – the final fission barrier

9.5 Other nuclear reactor systems

Index